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Research Papers

Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant

[+] Author and Article Information
Jun Wang

College of Engineering,
e-mail: Jwang564@wisc.edu

Mckinleigh Mccabe

College of Engineering,
The University of Wisconsin-Madison,
Madison, WI 53706
e-mail: Mckinleigh.f.mccabe@sargentlundy.com

Troy Christopher Haskin

College of Engineering,
The University of Wisconsin-Madison,
Madison WI 53706
e-mail: troy@hask.in

Yingwei Wu

Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
e-mail: wyw810@mail.xjtu.edu.cn

Guanghui Su

Nuclear Science and Technology,
Xi'an Jiaotong University,
Xi'an 710049, Shaanxi, China
e-mail: ghsu@mail.xjtu.edu.cn

Michael L. Corradini

College of Engineering,
The University of Wisconsin-Madison,
Madison, WI 53706
e-mail: corradini@engr.wisc.edu

1Corresponding authors.

Manuscript received October 17, 2017; final manuscript received July 10, 2018; published online September 10, 2018. Assoc. Editor: Jovica R. Riznic.

ASME J of Nuclear Rad Sci 4(4), 041002 (Sep 10, 2018) (9 pages) Paper No: NERS-17-1163; doi: 10.1115/1.4040887 History: Received October 17, 2017; Revised July 10, 2018

Accident tolerant fuels (ATF) and steam generator (SG) auxiliary feedwater (AFW) extended operation are two important methods to increase the coping time for nuclear power plant safety response. In light of recent efforts to investigate such methods, we investigate both FeCrAl cladding oxidation kinetics and SG AFW sensitivity analyses, for the Surry nuclear power plant Short-Term Station Blackout simulation using the MELCOR YR 1.8.6 systems code. The first part describes the effects of FeCrAl cladding oxidation kinetics. Zircaloy cladding and two different oxidation models of FeCrAl cladding are compared. The initial hydrogen generation time (>0.5 kg) is used as the evaluation criterion for fuel degradation in a severe accident. Results showed that the more recent oxidation correlation by ORNL predicts much less hydrogen generation than Zircaloy cladding. The second part investigates the effects of three different methods of AFW injection into the SG secondary side. We considered three different methods of water injection; i.e., constant water injection into the secondary side (case 1); water injection based on secondary side water level in boiler region (case 2); water injection based on secondary side water level in the downcomer region (case 3). The case of constant water injection is the most straightforward, but it would have the tendency to overfill the SG with excess water. Water injection with downcomer level control is more reasonable but requires DC power to monitor level and to control AFW injection rate.

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Figures

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Fig. 8

Total mass of hydrogen

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Fig. 9

First and the secondary circuit pressure

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Fig. 10

Water levels in pressure vessels

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Fig. 7

Hydrogen production rate

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Fig. 6

Surry NPP system and core nodalization [5] (Reprinted with permission from Elsevier © 2017)

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Fig. 5

FeCrAl steam oxidation data of ORNL model [5] (Reprinted with permission from Elsevier © 2017)

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Fig. 4

Variation tendencies of density with temperature changes [5] (Reprinted with permission from Elsevier © 2017)

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Fig. 3

Variations of the thermal conductivity with temperature changes [5] (Reprinted with permission from Elsevier © 2017)

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Fig. 2

Variations tendency of specific heat with temperature changes [5] (Reprinted with permission from Elsevier © 2017)

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Fig. 1

Variations of enthalpy along with temperature changes [5] (Reprinted with permission from Elsevier © 2017)

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Fig. 11

Water level of the down-comer

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Fig. 23

Peak core temperature (AFW failure at 9 h)

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Fig. 12

Lower head temperatures

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Fig. 13

Debris mass through vessel

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Fig. 14

Containment pressure

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Fig. 15

SG water level (AFW failure at 9 h)

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Fig. 16

RPV water level (AFW failure at 9 h)

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Fig. 17

Primary system pressure (AFW failure at 9 h)

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Fig. 18

Peak core temperature (AFW failure at 9 h)

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Fig. 19

Hydrogen mass generated (AFW failure at 9 h)

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Fig. 20

RPV water level (AFW failure at 9 h)

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Fig. 21

SG water level (AFW failure at 9 h)

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Fig. 22

Primary system pressure (AFW failure at 9 h)

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Fig. 24

Hydrogen mass generated (AFW failure at 9 h)

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